GB1510432A - Method for flattening the curve of evolution of heat of fuel elements within the core of a fast reactor - Google Patents

Method for flattening the curve of evolution of heat of fuel elements within the core of a fast reactor

Info

Publication number
GB1510432A
GB1510432A GB2540/76A GB254076A GB1510432A GB 1510432 A GB1510432 A GB 1510432A GB 2540/76 A GB2540/76 A GB 2540/76A GB 254076 A GB254076 A GB 254076A GB 1510432 A GB1510432 A GB 1510432A
Authority
GB
United Kingdom
Prior art keywords
diameter
fuel
core
fissile material
axial passage
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Expired
Application number
GB2540/76A
Other languages
English (en)
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Electricite de France SA
Original Assignee
Electricite de France SA
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Electricite de France SA filed Critical Electricite de France SA
Publication of GB1510432A publication Critical patent/GB1510432A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C1/00Reactor types
    • G21C1/02Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders
    • G21C1/022Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders characterised by the design or properties of the core
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02Fuel elements
    • G21C3/04Constructional details
    • G21C3/16Details of the construction within the casing
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C9/00Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G21C9/02Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
GB2540/76A 1975-02-10 1976-01-22 Method for flattening the curve of evolution of heat of fuel elements within the core of a fast reactor Expired GB1510432A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR7504112A FR2300398A1 (fr) 1975-02-10 1975-02-10 Procede d'aplatissement de la courbe d

Publications (1)

Publication Number Publication Date
GB1510432A true GB1510432A (en) 1978-05-10

Family

ID=9151006

Family Applications (1)

Application Number Title Priority Date Filing Date
GB2540/76A Expired GB1510432A (en) 1975-02-10 1976-01-22 Method for flattening the curve of evolution of heat of fuel elements within the core of a fast reactor

Country Status (4)

Country Link
US (1) US4372911A (enrdf_load_stackoverflow)
DE (1) DE2605002C3 (enrdf_load_stackoverflow)
FR (1) FR2300398A1 (enrdf_load_stackoverflow)
GB (1) GB1510432A (enrdf_load_stackoverflow)

Families Citing this family (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS58200193A (ja) * 1982-05-18 1983-11-21 動力炉・核燃料開発事業団 中空ペレツトを用いる核燃料棒
DE3670923D1 (de) * 1985-01-29 1990-06-07 Framatome Sa Kern eines schnellen kernreaktors mit einem einzigen typ von brennstoffbuendeln.
FR2581232B2 (fr) * 1985-04-25 1987-06-05 Novatome Coeur de reacteur nucleaire a neutrons rapides comportant un seul type d'assemblages de combustible nucleaire
US4687629A (en) * 1986-01-27 1987-08-18 Westinghouse Electric Corp. Fuel rod with annular nuclear fuel pellets having same U-235 enrichment and different annulus sizes for graduated enrichment loading
US4994233A (en) * 1989-01-27 1991-02-19 Westinghouse Electric Corp. Fuel rod with axial regions of annular and standard fuel pellets
EP2869306A1 (en) * 2013-10-30 2015-05-06 Thor Energy AS A fuel assembly for a nuclear reactor

Family Cites Families (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
NL244977A (enrdf_load_stackoverflow) * 1958-11-04 1900-01-01
US3446703A (en) * 1967-11-15 1969-05-27 Atomic Energy Commission Method of operating a nuclear reactor
GB1285464A (en) * 1969-08-08 1972-08-16 Atomic Energy Authority Uk Improvements in or relating to nuclear reactors
US3740314A (en) * 1972-01-28 1973-06-19 Atomic Energy Commission Fuel pin for a liquid-metal-cooled fast-breeder nuclear reactor
GB1446086A (en) * 1972-12-20 1976-08-11 Electricite De France Method for the passive protection of a nuclear reactor

Also Published As

Publication number Publication date
FR2300398A1 (fr) 1976-09-03
DE2605002A1 (de) 1976-08-19
DE2605002B2 (de) 1977-08-25
US4372911A (en) 1983-02-08
FR2300398B1 (enrdf_load_stackoverflow) 1982-05-21
DE2605002C3 (de) 1978-04-27

Similar Documents

Publication Publication Date Title
EP0379947B2 (en) Fuel rod for use in a nuclear fuel assembly
US3255092A (en) Control rods
US3145149A (en) Boiling nuclear reactor and fuel element therefor
US4636352A (en) Nuclear fuel rod with burnable plate and pellet-clad interaction fix
GB1507970A (en) Fuel arrangement for high temperature gas cooled reactor
GB1119990A (en) Nuclear reactor
US3712852A (en) Nuclear reactor control rod
US3103476A (en) Fuel element with burnable poison within the cladding
US4678629A (en) Nuclear fuel pellet containing gadolinia
GB1510432A (en) Method for flattening the curve of evolution of heat of fuel elements within the core of a fast reactor
US3260649A (en) Nuclear reactor
GB1062247A (en) Long lifetime nuclear reactor
KR910003800B1 (ko) 높은 우라늄 이용도를 갖는 핵연료 봉
GB1169714A (en) Nuclear Reactor Fuel Elements
GB1446086A (en) Method for the passive protection of a nuclear reactor
US4587089A (en) Fuel assembly for boiling water reactor
JP2556876B2 (ja) 燃料要素及び燃料集合体
GB1060999A (en) Liquid metal fast breeder reactor
US4120752A (en) Mixed oxide fuel pellet for fuel rod of nuclear reactor core
KR20210116677A (ko) 가연성 흡수제를 갖거나 갖지 않는 sps/fast 우라늄 연료를 사용한 소결
Reeve Ceramics as nuclear reactor fuels
US3111477A (en) Fuel element
JPS6443792A (en) Core and initially loaded core of nuclear reactor
US3253997A (en) Nuclear reactor and cooling and moderating arrangement therefor
GB1077385A (en) An improved method of operating a nuclear reactor

Legal Events

Date Code Title Description
PS Patent sealed [section 19, patents act 1949]
PCNP Patent ceased through non-payment of renewal fee
728C Application made for restoration (sect. 28/1977)
728U Case decided by the comptroller (sect. 28/1977)
728B Application made to the patents court (sect. 28/1977)
728I Application to the court of appeal (sect. 28/1977)